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MONTHYEARML20141G4611997-07-0303 July 1997 Forwards Final Results of CEOG Task 902 Best Estimated Copper & Nickel Weld Values for DPC C-E Fabricated Vessels, in Response to GL 92-01,Rev 1,Suppl 1 Project stage: Other 1997-07-03
[Table View] |
Forwards Final Results of CEOG Task 902 Best Estimated Copper & Nickel Weld Values for DPC C-E Fabricated Vessels, in Response to GL 92-01,Rev 1,Suppl 1ML20141G461 |
Person / Time |
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Site: |
Catawba, McGuire, Mcguire |
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Issue date: |
07/03/1997 |
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From: |
Tuckman M DUKE POWER CO. |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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GL-92-01, GL-92-1, TAC-M92659, TAC-M92660, TAC-M92694, TAC-M92695, NUDOCS 9707080137 |
Download: ML20141G461 (9) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 1999-09-09
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.. ll l "M Af.S Tuarva fa j kni ! Mce he&nt Charicite, NC282011006 NuclearGenemon (704)38722000 nice (701)3824360 Fax
) DUKEPOWER July 3,1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk ,
Washington, D.C. 20555 l
Subject:
Catawba Nuclear Station Units 1 & 2 !
Docket Nos. 50 -413, 414 TAC Nos. M92659 & M92660 McGuire Nuclear Station Units 1 & 2 i Docket Nos. 50 -369, 370 l TAC Nos. .M92694 & M92695 l Generic Letter 92-01, Revision 1, Supplement 1 l Request for Additional Information Concerning Data That Resulted From the Owners Groups' ]
Reactor Vessel Integrity Programs In the Closecut Letters for Generic Letter 92-01, Revision 1, Supplement 1, dated July 29, 1996 for Catawba Nuclear Station and July 31, 1996 for McGuire Nuclear Station, the NRC requested that Duke provide the results of the ongoing Owners Groups' RPV integrity programs relative to our plants.
The NRC was specifically referring to Task 902 of the C-E Owners Group (CEOG), Reactor Vessel Working Group (RVWG).
In Task 902, the CEOG went back through the manufacturing logs and all other known test data and developed best estimated copper and nickel values for all C-E fabricated reactor vessel welds. McGuire Unit 1 and Catawba Unit 2 reactor vessels were fabricated by C-E. This work has been completed and reviewed. There are no changes that would significantly impact Duke Power. ,
The final results of the CEOG Task 902 best estimated hkCOI /
copper and nickel weld values for the Duke Power C-E fabricated vessels are attached. The results of CEOG Task 902 confirm that Duke was using appropriate values that are 9707000137 970703 PDR ADOCK 05000369' P PDR lllllllllfllll llll l
. s U.S. NRC July 3,1997 Page 2 within the recommended range of final C-E values and are bounded by the specific recommended CEOG values. Duke has concluded that there is no need to make revisions to the previously submitted evaluations concerning reactor pressure vessel integrity and that the LTOP and P-T limits in the Technical Specifications remain valid. These evaluations were in accordance with the requirements of 10 CFR 50.60, 10 CFR 50.61 and Appendices G and H to 10 CFR Part 50.
Should you have any questions or require any additional information regarding this subject, please call Allison Jones-Young at (704) 382-3154.
Very truly yours,
. . [\ VLYM-M.S. Tuckman Senior Vice President Nuclear Generation Enclosures xc: L.A. Reyes Regional Administrator, Pegion II V. Nerses, ONRR P.S. Tam,'ONRR S.M. Shaeffer Senior Resident Inspector (MNS)
R.J. Freudenberger Senior Resident Inspector (CNS)
A
ENCLOSURE 1 TIIIS ENCLOSURE PROVIDES TIIE INFORMATION REQUESTED IN SUPPLEMENT 1, REVISION 1 OF GENERIC LETTER (GL) 92-01 CLOSE OUT LETTER FOR MCGUIRE UNIT 1.
McGuire Unit ~1'And Sister Plant Weld Information for Lower Shell Long.
Seams,~3-442 A, B & C (Heat No. 21935 and 12008, Linde 1992 Flux) '
Plant Component Data Pt.- Wt% Wi%. Reference
. No. -Cu Ni- l McGuire 1 Lwr. Shell Long Weld I,2 Salem 2 Lwr. Shell Long Weld 3 C-E MML Supplemental Test 1 0.20 8-0,86 4, 5 Analysis C-E MML Supplemental Test 2 0.22 6 Analysis Diablo Canyon 2 Inter. Shell Long. Weld 7 Diablo Canyon 2 Upr. Shell Long. Weld 8 Diablo Canyon 2 Beltline Weld Repair 3 0.23 0.90 9,10 Diablo Canyon 2 Beltline Weld Repair 4 0.21 0.76 9,10 Diablo Canyon 2 Beltline Weld Repair 5 0.22 0.90 9,10 Average Chemistry (Beltline Weld Repair) 0.22 0.85 Diablo Canyon 2 Surveillance Weld 6 0.22 0.83 11 Diablo Canyon 2 Surveillance Weld 7 0.219 0.86 12 Diablo Canyon 2 Surveillance Weld 8 0.212 0 88 12 i Diablo Canyon 2 Surveillance Weld 9 0.213 0.90 12 Diablo Canyon 2 Surveillance Weld 10 0.225 0.875 13 Diablo Canyon 2 Surveillance Weld 1I 0.213 0.856 13 Diablo Canyon 2 Surveillance Weld 12 0.225 0.877 13 Diablo Canyon 2 Surveillance Weld 13 0.196 0.763 14 Diablo Canyon 2 Surveillance Weld 14 0.240 0.958 14 Diablo Canyon 2 Surveillance Weld 15 0.230 0.910 14 Surveillance Weld Average 0.22 0.87 mm SOverall' Average t , -. 4 ,. & t 0.221 70.86; > -
- note: During the CEOG review it was discovered that the 0.86% Ni value referenced in the Salem report is actually an averaged value, not a data point from D7525 as stated. The weighted average above still remains the same once this value is dropped.
CEOG Task 902 Values (Referer.ce 36):
Heat No. 21935 and 12008, Linde 1092 Flux Sample weighted mean: 0.213% Cu and 0.867% Ni i 1
j
l McGuire Unit 1 And Sister Plant Weld Information for Intermediate Shell
~ Lo'ng. Seams,2-442 A, B & C (Heat No. 20291 and 12008, Linde 1992 Flux) l l Plant Component . Data Wt% Wt% Reference Pt.# .Cu Ni McGuire ! Int. Shell Long Weld 15,16,1 Calvert Cliffs 1 Int. Shell Long Weld 7 McGuire i Supplemen'.al Test 1 0.19 0.89 17 McGuire 1 Surveillance Weld 2 0.21 0 88 18 McGuire 1 Surveillance Weld 3 0.20 0.91 19 McGuire i Surveillance Weld 4 0.20 0.87 20,21 McGuire i Surveillance Weld 5 0.19 0.85 20,21 McGuire 1 Surveillance Weld 6 0.19 0.86 20,21 McGuire 1 Average 0.20 0.88 Pilgrim 1 CVN Specimen Y4A 7 0.14 0.81 22,23 Pilgrim 1 CVN Specimen Y45 8 0.16 0.81 22,23 Pilgrim i CVN Specimen Y5M 9 0.17 0.78 22,23 Pilgrim i CVN Specimen Y6U 10 0.17 0.81 22,23 Pilgrim i CVN Specimen Y6Y l1 0.16 0.77 22,23 Pilgrim i CVN Specimen Y61 12 0.16 0.79 22,23 Pilgrim 1 CVN Specimen Y65 13 0.17 0.80 22,23 Pilgrim 1 CVN Specimen Y66 14 0.16 0.77 22,23 Pilgrim i CVN Specimen Y4A 15 0.16 0.79 22,23 Pilgrim 1 CVN Specimen Y4A 16 0.16 0.81 22,23 Pilgrim i ID, Surveillance Weld 17 0.17 0.98 23,24 Pilgrim I ID, Surveillance Weld 18 0.16 0.94 23,24 Pilgrim i T/4, Surveillance Weld 0.16 0.96 23,24 19 ..~
Pilgrim 1 T/4, Surveillance Weld 20 ul3 0.72 23,24 Pilgrim 1 T/4, Surveillance Weld 21 a19 0.86 23,24 Pilgrim 1 T/2, Surveillance Weld 22 0.17 0.76 23,24 Pilgrim 1 T/2, Surveillance Weld 23 0.16 0.79 23,24 Pilgrim 1 3T/4, Surveillance Weld 24 0.18 0.93 23,24 Pilgrim 1 3T/4, Surveillance Weld 25 0.17 0.95 23,24 Pilgrim 1 3T/4, Surveillance Weld 26 0.19 0.83 23,24 Pilgrim 1 OD, Surveillance Weld 27 0.17 0.97 23,24 Pilgrim i OD, Surveillance Weld 28 0.13 0.74 23,24 Pilgrim 1 Average 0.16 0.84 Overall Average 0.18 l 0.86 CEOG Task 902 Values (Reference 36):
Heat No. 20291 and 12008, Linde 1092 Flux j Sample weighted mean: 0.199% Cu and 0.846% Ni
l McGuire Unit 1 And Sister Plant Weld Information for Intermediate To Lower Shell Circumferential Weld,9-442 (IIcat No. 83640, Linde 0091 Flux)
Plant Component - Data Pt. Wt% Wi% Reference No. Cu Ni j Almarez 1 Surveillance Weld 1 .05 .120 25 l D-12745 2 .05 ---
26 D-23725 3 .06 .04 7 D-14090 4 .05 --
27 McGuire 1 Int / Lwr. Shell Cire. Weld 28 Farley 2 Lwr. Shell Long. Weld 29 Overall Average 0.05 0.08 i
_CEOG Task 902 Values (Reference 36_);
Heat No. 83640, Linde 0091 Flux Simple mean: 0.051% Cu and 0.096% Ni
4 ENCLOSURE 2 Tills ENCLOSURE PROVIDES TIIE INFORMATION REQUESTED IN SUPPLEMENT 1, REVISION 1 OF GENERIC LETTER (GL) 92-01 CLOSE OUT LETTER FOR CATAWBA UNIT 2.
Catawba Unit 2 The Catawba Unit 2 reactor pressure vessel was manufactured by C-E in Chattanooga, Tennessee.
The vessel was ordered by Westinghouse Electric Corporation under C-E Contract 8871. The weld wire (not Cu coated) used to fabricate the beltline welds was low in Cu and Ni content. As a result of the low Cu/Ni weld in the Catawba Unit 2 vessel, it is plate limited for 10 CFR 50.61 RTPTS at EOL and is plate controlled for the current P-T limit curves and LTOP analysis. The most limiting weld material calculated EOL RTPTS using surveillance capsule data is 4.5 F which is over 200 F below the 10CFR50.61 screening criteria. With these low EOL RTPTS values and plate limited critical material, this additional information is oflittle value for detennining the structural integrity of the reactor vessel since it is controlled by the plate properties.
] Catawba Unit 2 Beltline Weld Material (IIcat No. 83648, Linde 0091 Flux)
Plant _ Component - Data Pt.' Wt % - Wt % Reference No. Cu Ni Catawba 2 Surveillance Program i 0040 o. I 40 37,39 Catawba 2 Surveillance Program 2 0.036 0.140 37,39 Catawba 2 Surveillance Program 3 0 051 0.180 37,40 CE Original Weld Cert. Job Number D32255 0.040 37,41 Overall Combined Average l 0.042 l 0.153 l l 4
CEOG Task 902 Values (Reference 36h Heat No. 83648, Linde 0091 Flux Simple mean: 0.042% Cu and 0.136% Ni
.-_ _- _. _ _ _ . . ~_ - . - . _. -
l l
i REFERENCES
- 1. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 3-442 A, February 24,1970.
- 2. Weld inspection Record, Combustion Engineering Contract & Unit No. 2167 Seam No. 3-442 B, February 24,1970.
l l 3. Response to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, 10CFR50.54(f), Salem Generating Station Unit Nos. I and 2, Public Service Electric & Gas Company, June 30,1992.
- 4. Salem Units 1 & 2, Reactor Vessel Weld Data, Combustion Engineering Report Prepared for Public Service Electric & Gas Co, November 1985.
- 5. Welding Materials Qualifications to Requirements of ASME, Section 111, Wire Heat No.
21935 & 12008, Sample No. D-7525, Combustion Engineering Metallurgical Research and Development Department, October 27,1969.
- 6. Welding Materials Qualifications to Requirements of ASME, Section Ill, Wire Heat Nos.
21935 & 12008, Sample No. D-7278, Combustion Engineering Metallurgical Research and Development Department, August 12,1969.
- 7. RPVDATA Reactor Vessel Materials Database, developed by ATI Consulting, Version 1.2, August 28,1995.
- 8. Evaluation of Diablo Canyon Pmver Plant Reactor Vessel Materials by the NRC Pressurized Thermal Shock Screening Criteria, Pacific Gas and Electric Department of Engineering Research, Report 420-85.687, Revision 1, January 13,1986.
- 9. Evaluation of Diablo Canyon Units I and 2 Reactor Vessel Beltline Weld Chemistry, Westinghouse Electric Corp., WCAP-10472, Septembcr 1983.
10.WCAP-10755,"Diablo Canyon Unit 2 Flux Reduction Program for Reactor Vessel Integrity Phase 1," R.L. Turner, et al., Westinghouse Electric Corp., July 1995.
I 1. Pacific Gas and Electric Company Diablo Canyon Unit No. 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-8783, December 1976.
- 12. Analysis of Capsule U from the Pacific Gas and Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-11851, May 1988.
- 13. Analysis of Capsule X from the Pacific Gas & Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-12811, December 1990.
14.WCAP-14363," Analysis of Capsule Y from the Pacific Gas and Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program," E. Terek, et al., May 1995.
a
- 15. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 2-442'B, April 22,1969.
. 16. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 2-442 C, April 22,1969.
17." Chemical Analysis of Weld Metal Specimens for Baltimore Gas & Electric Company,"
Wylie Laboratories Report No. 40602-04, July 27,1989.
- 18. Duke Power Company William B. McGuire Unit No.1 Reactor Vessel Surveillance Program, Westinghouse Electric Corp., WCAP-9195, November 1977.
19 Analysis of Capsule U from the Duke Power Company McGuire Unit i Reactor Vessel
! Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-10786, February 1985.
- 20. Evaluation of Pressurized Thermal Shock for McGuire Unit 1, Westinghouse Electric Corp.,
WCAP-13948, May 1994.
- 21. Westinghouse Electric Corporation Nuclear Service Division CMT- Analytical Laboratory, i Waltz Mill Site, Analytical Request #15211, Alloy Analysis - Steel, Duke Power Company McGuire Nuclear Plant Unit 1, Lawrence Kardos, November 15,1993.
22.Perrin, J.S., et al.," Evaluation of Mechanical Properties of Unitradiated Specimens from Pilgrim Unit No.1,"Battelle Columbus Laboratories, October 1979.
23." Reactor Vessel Weld Metal Chemical Composition Variability Study for Baltimore Gas &
Electric Company," B&W Nuclear Technologies, BAW-2220, June 1995.
- 24. " Pilgrim Surveillance Program Weld Documentation", Combustion Engineering, Report No.
B-PENG-ER-002, February 1994.
- 25. Weld inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 9-442, September 17,1972.
- 26. Central Nuclear de Almarez, Almarez Unit No.1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-8819, December 1976.
- 27. Welding Materials Quali0 cations to Requirements of ASME, Section lit, Wire Heat No.
83640, Sample No. D-12745, Combustion Engineering Metallurgical Resem ;a a nd Development Department, August 17,1972.
- 28. Welding Materials Quali0 cations to Requirements of ASME,Section III, Wire Heat No. l 83640, Sample No. D-23725, Combustion Engineering Metallurgical Research and Development Department, March 25,1976.
- 29. Welding Materials Quali0 cations to Requirements of ASME, Section 111, Wire Heat No.
83640, Sample No. D-14090, Combustion Engineering Metallurgical Research and Development Department, January 30,1973.
- 30. WCAP-13763," Evaluation of Pressurized Thermal Shock For Catawba Unit I", P.A. Peter, dated August 1993. Submitted to the NRC by letter dated August 12,1993.
1
- 31. An'alysis of Capsule U from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-10786, February 1985.
- 32. Analysis of Capsule X from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-12354, August 1989.
J J 33. Evaluation of Diablo Canyon Units I and 2 Reactor Vessel Beltline Weld Chemistry.
Westinghouse Electric Corp., WCAP-10472, September 1983.
- 34. Analysis of Capsule V Specimens and Dosimeters and Analysis of Capsule Z Dosimeters from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-13949, February 1994.
- 35. WCAP-13518," Evaluation of Pressurized Thermal Shock For McGuire Unit 2", J. M.
Chicots, dated October 1992.
- 36. CE NPSD - 1039 Rev.1, Final Report,"Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds", CEOG Task 902, Prepared for the C-E Owners Group, April 1997,
- 37. WCAP-13874," Evaluation of Pressurized Thermal Shock For Catawba Unit 2", P.A. Peter, 2
dated February 1994. Submitted to the NRC by letter dated March 2,1994.
l 38. WCAP-13875," Analysis of Capsule X From the Duke Power Company Catawba Unit 2 Reactor Vessel Radiation Surveillance Program", E. Terek, S. L. Zawalick, A. Madeyski, P.A.
Peter, dated February 1994. Submitted to the NRC by letter dated March 2,1994.
- 39. WCAP-10868," Duke Power Company Catawba Unit No. 2 Reactor Vessel Radiation Surveillance Program", L. R. Singer, November 1985.
- 40. WCAP-11941," Analysis of Capsule Z from the Duke Power Company Catawba Unit No. 2 Reactor Vessel Radiation Surveillance Program", S. E. Yanichko, September 1988.
- 41. Letter from Combustion Engineering, Inc. to Westinghouse," Core Region Weld Materials Contract 161053/8871 & 161054/8971", M. C. Herder, dated April 8,1974 and Combustion Engineering Metallurgical Research and Development Department - Chattanooga, Welding Material Qualification to requirements of ASME Section III, Job Number D3225, project Number 960009, December 12,1972.